ML20249A997

Amend 47 to License SNM-696 for General Atomics

ML20249A997
Person / Time
Site:	07000734
Issue date:	06/04/1998
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20249A996	List: ML20249A995 ML20249A997 ML20249B000
References
NUDOCS 9806190254
Download: ML20249A997 (8)

Text

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U.S. NUCLEAR REGULATORY CO\tMISSION MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, ChapterJ, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated '

below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the

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Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.

Licensee

1. General Atomics 3. License Number SNM-696, Amendment 47

2. P.O. Box 85608 4. Expiration Date December 31,1989 San Diego, Califomia 92186-9784 5. Docket No.70-734

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6. Byproduct Source, and/or LChemical and/or Physical 8. Maximum amount that Licensee 3

Special Nuclear Material M Form *p May Possess at Any One Time T Under This License vs . ,

A. Uranium 4/ A.:$ Enriched up to,19,i99% A:g 200 kilograms U-235 N . U-235 i f O B. Uranium r-5 %(( . ? L N't.i B. ; Enriched 20,10100W B.Less than 5000 gm*

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&,.L5235( [(? / ;

U) 5 C. U-233 C. #A , ,C Less than 2000 gm Y'y ' 4 gAj 4'd op U-233*

Encapsulated andM D. Plutonium 4,O. leagous)ResE D. Less than 2000 gm total Pu*

E. Plutonium E. Bred but unseparated E. Less than 1000 gm total Pu*

F. Plutonium F. Plated calibration F. Less than 5 grams source total Pu*

G. Plutonium G. Solutions, precipitates G. Less than 5 grams solids and total Pu*

l The sum total quantity of strategic special nuclear material possessed at any one time must be less than 5,000 grams computed by the formula:

Grams = grams U-235 in uranium enriched to 20% or more plus 2.5 (grams U-233 + grams plutonium) 9906190254 990604 PDR ADOCK 07000734 C PDR

NRC FORM 374A If.S. NL' CLEAR REGl'LATORY COMMISSION PAGE 2 of 8 PAGES License Number SNM-696 oocket or Rererence Number MATERIALS LICENSE SUPPLEMENTARY SHEET 70-734 Amendment No. 47 i

9. Authorized place of use: The licensee's San Diego, California site as specified in the aforesaid application and supplements.

10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions.

These sections are part of the license, and the licensee is subject to compliance with all listed conditions in each section.

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e <;y y k < s y . 3 s .*, C M e j A 4 ** \o n FOR TAE NUCLEAR REGULATORY COMMISSION Y f-p p$

Date: I f8 M.

By, / Michael F. Weber '

// $ivision of Fuel Cycle Safety and Safeguards, NMSS Washington, DC 20555 (Provided w/ Amendment 31)

Enclosures:

1. License Condition for Leak Testing Sealed Plutonium Sources, dtd 4/93

2. License Condition for Plutonium Alpha Sources, dtd 4/93 i

3. Guidelines for Decontamination of Facilities..., dtd 4/93 l

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l NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 3 or 8 PAGES License Number SNM-696 Docket or Reference Number MATERIALS LICENSE SUPPLEMENTARY SIIEET 70-734 Ainendment No. 47 i

SAFETY CONDITIONS j S-1. Authorized use: For use in accordance with statements, representations, and conditions contained in Part ll " License Specifications" dated July 24,1981, and supplements dated March 16 and December 24,1982; February 4, November 14, and November 15,1983; April 10, April 12, June 28, September 4, and September 7,1984; December 5,1985; May 23, September 25, and December 10, 1986; December 21,1987; March 4, March 9 (2), March 22, April 26, August 22, September 8, and November 2,1988; May 25 and November 17,1989; June 27,1990; April 30 and September 27,1991; March 5, March 18, June 24, and September 10,1992; January 20,1995; and in the "SVA Decommissioning Plan" dated April 1,1990 (submitted by letter dated March 30,1990); August 22, 1990 (submitted by letter dated August 24 19 Group 6 Laboratories unrestricted;useir'eqb,es.90);

t8at94 August 12,1994; March June 15,1992; 1,1995; Group 7July 12 and Laboratories use requestunrestricted dated August use(1996; October

@& qqdest Idated 15,1996, and April 5,1995; December 30,1997; Group Group 98B Labor La unrestricted use request dated July 17,1997; Building 36L4boratories unrestricted use release dated July 25,1997, and Janukty 29; 1998; and Site Decomrnissi6ning Plan dated October 11 and December 5,1996; Ap*rikl8,1997;1 band Rgt,' Cell Decommissioning Plan dated April 22,1998. January Fr '& 15,(1; 4 N; , ,i C S-2. Records of all safety-rgted r,eporis%dfoaiyss's[f 1, shall be retained as follows:

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a. Copies of criticality 3nd ra$ation$qly stalys ,lhall tid retained for at least 2 years or for 6 is termindthd, WNch} ls long.

b.

months after a projgN e Copies of all other saf y4 elated recor'ds (e.g., p!

s alterations and additions, abnormal occurrences associated vlith fydigactivity regses, audits and inspections, instrument calibrations, ALARA findings, training and tethainidg,Srsonnel exposures, routine radiation and environmental surveys) shall be retained for at least 2 years or longer if required by regulations.

S-3. Notwithstanding the statements in Section 5.4.2 in the License Specification Volume (Part II), if double batching is not credible, the maximum safe batch size shall be no more than 75 percent of the minimum critical mass independent of the degree of water moderation and reflection. However, when the Th/U atomic ratio is 2 3.6 and the H/U s 20, the maximum safe batch size may be increased to 790 g contained U-235 independent of whether double batching is credible.

S-4. The Director QACD, upon recommendation of the appropriate manager within QACD, shall have authority to require immediate termination of activities and/or corrective action in any situation which, in their judgment, could lead to the unnecessary exposure of personnel to ionizing radiation, release of radioactive material, loss or damage of property, or non-compliance with the license or a regulation.

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 4 of Q PAGES License Number SNM-696 MATERIALS LICENSE Duka w Refenna Number

., SUPPLEMENTARY SHEET 70-734 Amendment No. 47 S-5. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall meet at least annually to review (1) reports of audits and inspections performed since the last ALARA review and (2) employee exposures and effluent release data to determine (a)if there are any upward trends developing in personnel exposures for identifiable categories of workers, types of operations, or effluent releases, (b)if exposures and releases might be lowered in accordance with the ALARA concept, and (c) if equipment for effluent and exposure control is being properly used, maintained, and inspected.

The CRSC evaluation, recommendations, and corrective actions shall be documented and the report shall be sent to the appropriate operations managers and ths Vice President, Finance and Administration.

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S-6. Radiological Work Permits (RgPS) shall be issue (dfogall unplanned or non-routine w material not covered by a yVA. The RWP shall be signed)y Health Physics management or a senior staff member before related work can commence. A serno.pstaff member shall be a Health Physics Technician having a minknum;of years' experience in radfytion safety. An evaluation of the safety effectiveness of the pe/mit shall 'made upon cod $letion o(fihe work.

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y $) :3-) (p S-7. Radiation safety trainip,xLappropr le o.theArppi [eb's ,

, g need2shall be given to all new emplo S-8. Radiation safety trainik ank c~ d $yllb~e chnhuct 'by the Health Physics Manager similarly qualified individDal. ., eU Mpager delegate training in that portion of the course to an individual who4 Ffis un'tbhresen @(y Y q. a 49 so S-9. Continuous air sampling sh e condu ir$ any ar here licensed material can become airbome.

S-10. The location of air samplers shall h adteofeedjenkually and whenever any process or equipment changes are made to verify the representativeness of work area air sampling. In addition, the location of air samplers shall be checked at the commencement of operations in any area that has been shutdown for more than 6 months to verify the representativeness of air sampling.

S-11. The laboratories in which plutonium in a dispersible form may be used shall have exhaust ventilation systems separate from other building exhausts and shall provide dual HEPA filtering of the effluent air.

S-12. Sealed Plutonium sources shall be subject to the leak testing and actions specified in the attached

" License Condition for Leak Testing Sealed Plutonium Sources," dated April 1993.

l Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for Plutonium Alpha Sources," dated April 1993.

S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report l whenever there is any new residential development within 1 mile around the site that constitutes a ,

significant change in parameters that may be affected by the release of radioactive materials into the environment.

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NCC FOM 374A US NUCLEAR RECULATORY COMMISSION PAGE 5 or C PAGES i License Number SNM-696 MATERIALS LICENSE Mew Rernence Numba

., SUPPLEMENTARY SHEET 70-734 Amendment No. 47 S-14 Deleted by Amendment 14 dated August 3,1990 (originally numbered S-23 in 1990 - 1992 and renumbered to S-14 in Amendment 23 dated October 7,1993). The information in License Condition S-23 was incorporated into License Condition S-9 by adding the date of May 25,1989; License

' Condition S-9 later became S-1.

S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, authorized as a place of use for special nuclear material, in accordance with the general decommissioning plan submitted by your letter dated July 25,1986, and its supplement dated October 15,1986, so that these facilities and grounds can be released for unrestricted use. The corporate commitment that funds will to made available for decommissioning the facility, provided by letter dated September 10,1986, is hereby incorporated as a condition R of the license.R E G f k l S-16. Release of equipment, faciliti ckages to the pfe,stricted area or to uncontrolled areas onsite shall be in accordance witty attached " Guidelines fdr contamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of L , ses for Byproduct, Source, or Special Nuclear Material," dated 4pril j993. Jg W d x f f S-17. Deleted by Amendmeh7, Sepj , r 1996: , A facif has been decommissioned and released for general use. s, ,i .

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S-18. Notwithstanding the shemM.. cjn.Ss3 ; Parti of the license, the trip levels will be readjusted

' ~ tem ift'he rm point fails to activate within after each5 monthly approximately secondporeithsriotestST the ctfucal@p r trial S-19. Notwithstanding the state in SectiNr 2.1.4, Pa of the license, no material handling shall be allowed in any area in which t e r3puired criticaligalarm system is inoperative.

Y Nr N S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and released for general use.

S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to the licensee on October 3,1988. i S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and released for general use.

S-23. The licensee shall maintain and execute the response measures described in the Emergency Plan dated October 10,1997, supplemented by letter dated November 6,1997, or as further revised by the licensee consistent with the provisions of 10 CFR 70.32(i).

S-24 The licensee shall develop individual survey plans for each facility or group of laboratories and provide NRC a 30-day notification, prior to GA initiating a final survey, to allow the NRC to schedule in-process

- inspections / surveys if required.

S-25 The licensee must submit for review and approval to NRC residual contamination and characterization data and planned decommissioning procedures for areas where

l NRC FORM 374 A US. NUCLEAR REGULATORY COMMISSION PAGE 6 of Q PAGES l License Number SNM-696 Docket or Reference Number MATERIALS LICENSE

., SUP,PLEMENTARY SHEET 70-734 Amendment No. 47

1. Decomrnissioning procedures will be required that have not been used by the licensee in previous decommissioning activities or have not been identified in the Site Decommissioning Plan dated October 11,1996, as amended December 5,1996; April 18,1997; and January 15, 1998;

2. Workers would be entenng areas where surface contamination and radiation levels are significantly higher than routinely encountered during previous decommissioning operations;

3. Procedures could result in significantly greater airborne concentrations of radioactive materials than have been present in previous decommissioning operations; or

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4. Procedures could result ig sigi1}fic'a'n'ti/ gger releases of radioactive material to the environment than thossessociated with previous decommissioning operations.

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NZC iORM 374A U.S. NUCIIAR RECOLATORY COMMISSION PAGE 7 of 8 PAGES I

License Number SNM-696 D cket or Reference Number

' MATERIALS LICENSE

., SUPPLEMENTARY SHEET 74734 Amendment No. 47 SAFEGUARDS CONDITIONS SECTION 1.0 - FACILITY ORGANIZATION l

Currently there is no license condition in this section. The necessary information has been incorporated into en epproved Fundamental Nuclear Material Control Plan, dated February 1998.

SECTION 2.0 - FACILITY OPERATION SG-2,1 Deleted by Amendment 37, Septembkr 1996. Not applicable under a possession only license.

cgB EGf SG-2.2 Deleted by Amendment 37.)S6ptember 1996'. kof applicable under a possession only license.

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SG-2.3 Deleted by Amendmerit 37, September 1996. Not apgcable under a possession only license.

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SG-2.4 Deleted by Amengent 37 ptemb r 996 ot applicgble under a possession only license.

SECTION 3.0 - MEASUREMENTS . i } [pd , j ;1 O IdI@l

[*h Noia l SG-3.1 Deleted by Amen lnent ble under a possessien only license.

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SG-3.2 Deleted by Amendment 37,' SeplE 199g; Not apgcable under a possession only license.

SG-3.3 Deleted by Amendme 'J7, September 1996. N[pplicable under a possession only license.

SECIlON 4.0 - MEASUREMENT CONTkOLb h -%t SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a pos 4,ssion only license.

SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. .

SG-4.8 Deleted by Amendment 37, September 1996. Not applicable under a possession only license. I l

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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE C of C PAGES License Nurnber SNM-696 Docket or Reference Number MATERIALS LICENSE 70- m

., SUPPLEMENTARY SHEET Amendment No. 47 i

SECILON 5.0 - INVENTORY SG-5.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-5.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-5.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SECTION 6.0 - RECORDS AND REPORTS SG-6.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license,

c. O SECIlON 7.0 - INTERNAL Q

CONTROLb' p.R H E G h>

SG-7.1 Deleted by Amendmeitt,37, September 1996. NOt [pgcable under a possession only lice 5 x

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SECIlON 8.0 - MANAGEMENT i f r t~ i' ',

?) 3 O SG-8.1 Deleted by Amer dment 37,I 'ernben19( Mot applihble under a possession onl r-Q -a

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': f SECT!ON 9.0 - PHYSICAL MOTbNIOhrRMI MMENTbYOR3nORMULA OUANTITIES OF STRATEGIC SEECIAL NUCf7AR II5kTERIAL C

y syCo ,/ fo SG-9.1 The licensee shall fdf sw the m{e]asures[ des)(p. .

di physical protection plan entitled, " Fixed Site and Transportatioff9pn for the' Protection ecial Nuclear Material of Moderate and Low Strategic Significance," dategay 1989, sujpiit by letter dated May 8,1989; and as it may be further revised in accordance wi0ttidprkis ons of 10 CFR 70.32(e).

SECTION -10.0 - TEMPORARY OR ONE_ TIME CONDITIONS SG-10.1 Deleted by Amendment 31, dated July 1995.

SG-10.2 Deleted by Amendment 31, dated July 1995.

SG-10.3 Deleted by Amendment 31, dated July 1995.

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